Plasma–wall interaction in laser inertial fusion reactors: novel proposals for radiation tests of first wall materials

Dry-wall laser inertial fusion (LIF) chambers will have to withstand strong bursts of fast charged particles which will deposit tens of kJ m−2 and implant more than 1018 particles m−2 in a few microseconds at a repetition rate of some Hz. Large chamber dimensions and resistant plasma-facing materials must be combined to guarantee the chamber performance as long as possible under the expected threats: heating, fatigue, cracking, formation of defects, retention of light species, swelling and erosion. Current and novel radiation resistant materials for the first wall need to be validated under realistic conditions. However, at present there is a lack of facilities which can reproduce such ion environments. This contribution proposes the use of ultra-intense lasers and high-intense pulsed ion beams (HIPIB) to recreate the plasma conditions in LIF reactors. By target normal sheath acceleration, ultra-intense lasers can generate very short and energetic ion pulses with a spectral distribution similar to that of the inertial fusion ion bursts, suitable to validate fusion materials and to investigate the barely known propagation of those bursts through background plasmas/gases present in the reactor chamber. HIPIB technologies, initially developed for inertial fusion driver systems, provide huge intensity pulses which meet the irradiation conditions expected in the first wall of LIF chambers and thus can be used for the validation of materials too.

Plasma–wall interaction in laser inertial fusion reactors: novel proposals for radiation tests of first wall materials

Dry-wall laser inertial fusion (LIF) chambers will have to withstand strong bursts of fast charged particles which will deposit tens of kJ m−2 and implant more than 1018 particles m−2 in a few microseconds at a repetition rate of some Hz. Large chamber dimensions and resistant plasma-facing materials must be combined to guarantee the chamber performance as long as possible under the expected threats: heating, fatigue, cracking, formation of defects, retention of light species, swelling and erosion. Current and novel radiation resistant materials for the first wall need to be validated under realistic conditions. However, at present there is a lack of facilities which can reproduce such ion environments. This contribution proposes the use of ultra-intense lasers and high-intense pulsed ion beams (HIPIB) to recreate the plasma conditions in LIF reactors. By target normal sheath acceleration, ultra-intense lasers can generate very short and energetic ion pulses with a spectral distribution similar to that of the inertial fusion ion bursts, suitable to validate fusion materials and to investigate the barely known propagation of those bursts through background plasmas/gases present in the reactor chamber. HIPIB technologies, initially developed for inertial fusion driver systems, provide huge intensity pulses which meet the irradiation conditions expected in the first wall of LIF chambers and thus can be used for the validation of materials too.

Recrystallization of amorphous nano-tracks and uniform layers generated by swift-ion-beam irradiation in lithium niobate.

The thermal annealing of amorphous tracks of nanometer-size diameter generated in lithium niobate (LiNbO3) by Bromine ions at 45 MeV, i.e., in the electronic stopping regime, has been investigated by RBS/C spectrometry in the temperature range from 250°C to 350°C. Relatively low fluences have been used (<1012 cm−2) to produce isolated tracks. However, the possible effect of track overlapping has been investigated by varying the fluence between 3×1011 cm−2 and 1012 cm−2. The annealing process follows a two-step kinetics. In a first stage (I) the track radius decreases linearly with the annealing time. It obeys an Arrhenius-type dependence on annealing temperature with activation energy around 1.5 eV. The second stage (II) operates after the track radius has decreased down to around 2.5 nm and shows a much lower radial velocity. The data for stage I appear consistent with a solid-phase epitaxial process that yields a constant recrystallization rate at the amorphous-crystalline boundary. HRTEM has been used to monitor the existence and the size of the annealed isolated tracks in the second stage. On the other hand, the thermal annealing of homogeneous (buried) amorphous layers has been investigated within the same temperature range, on samples irradiated with Fluorine at 20 MeV and fluences of ∼1014 cm−2. Optical techniques are very suitable for this case and have been used to monitor the recrystallization of the layers. The annealing process induces a displacement of the crystalline-amorphous boundary that is also linear with annealing time, and the recrystallization rates are consistent with those measured for tracks. The comparison of these data with those previously obtained for the heavily damaged (amorphous) layers produced by elastic nuclear collisions is summarily discussed.

Amorphization kinectics under swift heavy ion irradiation: a cumulative overlapping-track approach

A simple illustrative physical model is presented to describe the kinetics of damage and amorphization by swiftheavyions (SHI) in LiNbO3. The model considers that every ion impact generates initially a defective region (halo) and a full amorphous core whose relative size depends on the electronic stopping power. Below a given stopping power threshold only a halo is generated. For increasing fluences the amorphized area grows monotonically via overlapping of a fixed number N of halos. In spite of its simplicity the model, which provides analytical solutions, describes many relevant features of the kinetic behaviour. In particular, it predicts approximate Avrami curves with parameters depending on stopping power in qualitative accordance with experiment that turn into Poisson laws well above the threshold value

Interstitial defects stability in FeCr alloys vs Cr concentration

Finding adequate materials to withstand the demanding conditions in the future fusion and fission reactors is a real challenge in the development of these technologies. Structural materials need to sustain high irradiation doses and temperatures that will change the microstructure over time. A better understanding of the changes produced by the irradiation will allow for a better choice of materials, ensuring a safer and reliable future power plants. High-Cr ferritic/martensitic steels head the list of structural materials due to their high resistance to swelling and corrosion. However, it is well known that these alloys present a problem of embrittlement, which could be caused by the presence of defects created by irradiation as these defects act as obstacles for dislocation motion. Therefore, the mechanical response of these materials will depend on the type of defects created during irradiation. In this work, we address a study of the effect Cr concentration has on single interstitial defect formation energies in FeCr alloys.

On the Extension of the Analytic Nodal Diffusion Solver ANDES to Sodium Fast Reactors

Within the framework of the Collaborative Project for a European Sodium Fast Reactor, the reactor physics group at UPM is working on the extension of its in-house multi-scale advanced deterministic code COBAYA3 to Sodium Fast Reactors (SFR). COBAYA3 is a 3D multigroup neutron kinetics diffusion code that can be used either as a pin-by-pin code or as a stand-alone nodal code by using the analytic nodal diffusion solver ANDES. It is coupled with thermalhydraulics codes such as COBRA-TF and FLICA, allowing transient analysis of LWR at both fine-mesh and coarse-mesh scales. In order to enable also 3D pin-by-pin and nodal coupled NK-TH simulations of SFR, different developments are in progress. This paper presents the first steps towards the application of COBAYA3 to this type of reactors. ANDES solver, already extended to triangular-Z geometry, has been applied to fast reactor steady-state calculations. The required cross section libraries were generated with ERANOS code for several configurations. The limitations encountered in the application of the Analytic Coarse Mesh Finite Difference (ACMFD) method –implemented inside ANDES– to fast reactors are presented and the sensitivity of the method when using a high number of energy groups is studied. ANDES performance is assessed by comparison with the results provided by ERANOS, using a mini-core model in 33 energy groups. Furthermore, a benchmark from the NEA for a small 3D FBR in hexagonal-Z geometry and 4 energy groups is also employed to verify the behavior of the code with few energy groups.

Stochastic homogenization of the laser intensity to improve the irradiation uniformity of capsules directly driven by thousands laser beams

Illumination uniformity of a spherical capsule directly driven by laser beams has been assessed numerically. Laser facilities characterized by ND = 12, 20, 24, 32, 48 and 60 directions of irradiation with associated a single laser beam or a bundle of NB laser beams have been considered. The laser beam intensity profile is assumed super-Gaussian and the calculations take into account beam imperfections as power imbalance and pointing errors. The optimum laser intensity profile, which minimizes the root-mean-square deviation of the capsule illumination, depends on the values of the beam imperfections. Assuming that the NB beams are statistically independents is found that they provide a stochastic homogenization of the laser intensity associated to the whole bundle, reducing the errors associated to the whole bundle by the factor  , which in turn improves the illumination uniformity of the capsule. Moreover, it is found that the uniformity of the irradiation is almost the same for all facilities and only depends on the total number of laser beams Ntot = ND × NB.

An educational initiative between the Universidad Politécnica de Madrid and Spanish Young Generation in Nuclear (Jóvenes Nucleares): The Seminar of Nuclear Safety in Advanced Reactors

Jóvenes Nucleares (Spanish Young Generation in Nuclear, JJNN) is a non-profit organization and a commission of the Spanish Nuclear Society (SNE). The Universidad Politécnica de Madrid (Technical University of Madrid, UPM) is one of the most prestigious technical universities of Spain, and has a very strong curriculum in nuclear engineering training and research. Finishing 2009, JJNN and the UPM started to plan a new and first-of-a-kind Seminar in Nuclear Safety focused on the Advanced Reactors (Generation III, III+ and IV). The scope was to make a general description of the safety in the new reactors, comparing them with the built Generation II reactors from a technical point of view but simple and without the need of strong background in nuclear engineering to try to be interesting for the most number of people possible.

Thermal diffusion profile by NRA of Deuterium implanted in solid breeder blanket materials

This paper studies the relationship between aging, physical changes and the results of non-destructive testing of plywood. 176 pieces of plywood were tested to analyze their actual and estimated density using non-destructive methods (screw withdrawal force and ultrasound wave velocity) during a laboratory aging test. From the results of statistical analysis it can be concluded that there is a strong relationship between the non-destructive measurements carried out, and the decline in the physical properties of the panels due to aging. The authors propose several models to estimate board density. The best results are obtained with ultrasound. A reliable prediction of the degree of deterioration (aging) of board is presented. Breeder blanket materials have to produce tritium from lithium while fulfilling several strict conditions. In particular, when dealing with materials to be applied in fusion reactors, one of the key questions is the study of light ions retention, which can be produced by transmutation reactions and/or introduced by interaction with the plasma. In ceramic breeders the understanding of the hydrogen isotopes behaviour and specially the diffusion of tritium to the surface is crucial. Moreover the evolution of the microstructure during irradiation with energetic ions, neutrons and electrons is complex because of the interaction of a high number of processes.

Ion Beam irradiation of copper nitride: electronic vs elastic-collision mechanism

Copper nitride is a metastable material which results very attractive because of their potential to be used in functional device. Cu3 N easily decomposes into Cu and N2 by annealing [1] or irradiation (electron, ions, laser) [2, 3]. Previous studies carried out in N-rich Cu3 N films irradiated with Cu at 42MeV evidence a very efficient sputtering of N whose yield (5×10 3 atom/ion), for a film with a thickness of just 100 nm, suggest that the origin of the sputtering has an electronic nature. This N depletion was observed to be responsible for new phase formation ( Cu2 O) and pure Cu [4]

Lifetime of silica final lenses subject to HiPER irradiation conditions

The goal of the European laser fusion project, is to build an engineering facility for repetitive laser operation (HiPER 4a) and later a fusion reactor (HiPER 4b). A key aspect for laser fusion energy is the final optics. At the moment, it is based on silica transmission lenses located 8 m away from the chamber center. Lens lifetime depends on the irradiation conditions. We have used a 48 MJ shock ignition target for calculations. We have studied the thermo-mechanical effects of ions and X-rays on the lenses. Ions lead to lens melting and must therefore be mitigated. On the other hand, X-rays (~1% of the energy) does not produce either a significant temperature rise or detrimental stresses. Finally, we calculated the neutron flux and gamma dose rate on the lenses. Next, based on a simple model we studied the formation of color centers in the sample, which lead to optical absorption. Calculations show that simultaneous neutron and gamma irradiation does not significantly increase the optical absorption during the expected lifetime of the HiPER 4a facility. Under severe conditions (HiPER 4b), operation above 800 K or lens refreshing by thermal annealing treatments seem to assure adequate behavior.

Assessing the solar irradiation potential for solar photovoltaic applications in buildings at low latitudes ¿ Making the case for Brazil

In Brazil, a low-latitude country characterized by its high availability and uniformity of solar radiation, the use of PV solar energy integrated in buildings is still incipient. However, at the moment there are several initiatives which give some hints that lead to think that there will be a change shortly. In countries where this technology is already a daily reality, such as Germany, Japan or Spain, the recommendations and basic criteria to avoid losses due to orientation and tilt are widespread. Extrapolating those measures used in high latitudes to all regions, without a previous deeper analysis, is standard practice. They do not always correspond to reality, what frequently leads to false assumptions and may become an obstacle in a country which is taking the first step in this area. In this paper, the solar potential yield for different surfaces in Brazilian cities (located at latitudes between 0° and 30°S) are analyzed with the aim of providing the necessary tools to evaluate the suitability of the buildings’ envelopes for photovoltaic use

Analysis and optimization of propagation losses in LiNbO3 optical waveguides produced by swift heavy-ion irradiation

The propagation losses (PL) of lithium niobate optical planar waveguides fabricated by swift heavy-ion irradiation (SHI), an alternative to conventional ion implantation, have been investigated and optimized. For waveguide fabrication, congruently melting LiNbO3 substrates were irradiated with F ions at 20 MeV or 30 MeV and fluences in the range 1013–1014 cm−2. The influence of the temperature and time of post-irradiation annealing treatments has been systematically studied. Optimum propagation losses lower than 0.5 dB/cm have been obtained for both TE and TM modes, after a two-stage annealing treatment at 350 and 375∘C. Possible loss mechanisms are discussed.

Simulación atomística de metales líquidos y aleaciones para reactores de fusión nuclear = Atomistic simulation of liquid metals and alloys for nuclear fusion reactors

La presente tesis comprende un estudio de metales líquidos, Li, Pb y eutéctico Li17Pb en el ámbito de la tecnología de fusión nuclear. Uno de los problemas fundamentales en futuros reactores de fusión es la producción y extracción de tritio en la denominada envoltura regeneradora (blanket en inglés). Dicho blanket tendrá dos propósitos, la extracción del calor generado por las reacciones de fusión para su posterior conversión en energía eléctrica así como la producción de tritio para realimentar el proceso. Dicha producción se realizará mediante el “splitting” del Li con los neutrones provenientes de la fusión. Esta reacción produce tritio y helio por lo que la interacción del T y el He con el metal líquido, con los materiales estructurales así como con el He es un problema fundamental aun no bien entendido y de gran importancia para futuros diseños. Los capítulos 1 2 y 3 presentan una introducción a dichos problemas. El capítulo 1 introduce al lector en la tecnología de fusión nuclear. El segundo capítulo explica en mayor detalle el uso de metales líquidos en reactores de fusión, no solo en blankets sino también como primera pared, divertor etc, lo que se denomina en general “plasma facing materials”. Por último se ofrece una breve introducción a las técnicas de dinámica molecular clásica (CMD) y un breve resumen de los potenciales más usados. El estudio se ha llevado a cabo utilizando simulación atomística mediante potenciales semi-empíricos del tipo átomo embebido (EAM). La Tesis consta de 4 partes bien definidas. En primer lugar se verificó la idoneidad de los potenciales tipo EAM para simular las propiedades de los metales Li y Pb en fase líquida. Dicho estudio se detalla en el Capítulo 4 y en su extensión, el Apéndice 1, en el que se estudia los límites de validez de esta aproximación. Los resultados de dicho estudio han sido publicados y presentados en diversos congresos internacionales. Un resumen de la metodología seguida fue publicado como capítulo de libro en Technofusión 2011. Los resultados se presentaron en diversos congresos internacionales, entre ellos ICENES 2011, (Artículo en ICENES Proceedings) ICOPS-SOFE 2011, en una presentación oral etc. El trabajo ha sido aceptado recientemente en Journal of Nuclear Materiales (Fraile et al 2012). La segunda parte y más importante comprende el desarrollo de un potencial para el estudio de la mezcla de ambos metales. Éste es el trabajo más novedoso e importante dado que no existía en la literatura un potencial semejante. Se estudiaron dos aproximaciones distintas al problema, un potencial tipo EAM/cd y un potencial EAM/alloy. Ambos potenciales dan resultados satisfactorios para la simulación del eutéctico (y concentraciones de Li menores que el 17%). Sin embargo el sistema LiPb en todas las concentraciones es un sistema que se aparta enormemente de una solución ideal y dicho potencial no daba buenos resultados para mezclas PbLi con concentraciones de Li grandes. Este problema fue solventado mediante el desarrollo de un segundo potencial, esta vez tipo EAM/alloy (segunda parte del Capítulo 5). Dicho trabajo será enviado a Physical Review Letters o a Phys. Rev. B, y una extensión junto con un estudio detallado de las propiedades del eutéctico de acuerdo con nuestras simulaciones se enviará a continuación a Phys. Rev. B. En tercer lugar se estudió el problema de la difusividad del H en metales líquidos aprovechando distintos potenciales existentes en la literatura. El problema del H en metales líquidos es importante en metalurgia. En dicho capítulo se estudió la difusividad del H en Pd, Ni y Al con potenciales tipo EAM, y también con un potencial más sofisticado que tiene en cuenta la dependencia angular de las interacciones (ADP por sus siglas en inglés). De este modo disponemos de un estudio detallado del problema con diferentes modelos y diferentes metales. La conclusión apunta a que si se compara con los resultados experimentales (muy escasos) los resultados obtenidos mediante CMD dan valores bajos de la difusividad del H. Las razones de dicho desacuerdo entre simulación y experimentos se detallan en el Capítulo 6. Este trabajo ha sido presentado en una presentación oral en el reciente congreso internacional “Trends on Nanothecnology” TNT 2012 celebrado en Madrid. El trabajo será publicado en un futuro próximo. Por último, como se dijo anteriormente, el estudio del He, la formación de burbujas en metales líquidos, su difusión nucleación y cavitación es otro problema deseable de ser estudiado mediante técnicas atomísticas. Para ello es necesario el desarrollo de diversos potenciales, He-Li, He-Pb y un potencial ternario Pb-Li-He. Para ello se han realizado simulación ab initio de los sistemas Pb+He y Li+He. Dicho estudio pretende calcular las fuerzas entre los átomos del metal (Pb o Li) con intersticiales de He. De este modo aplicaremos el “force matching method” (FMM) para el desarrollo de dichos potenciales. En el Capítulo 7 se detallan los resultados obtenidos referidos a las posiciones más favorables de las impurezas de He dentro de redes cristalinas de Pb y Li así como el efecto de tener en cuenta el acoplo spin-orbita (SOC en inglés). El análisis de los resultados en términos de transferencia de carga y análisis de las densidades electrónicas, así como la creación de los potenciales mencionados está en progreso. En conjunto la tesis presenta un estudio de los diversos problemas relacionados con el uso de metales líquidos en reactores de fusión y representa un primer paso en la determinación de parámetros de gran importancia para el diseño de blankets y sistemas de primera pared. Con la simulación MD de dichos problemas mediante, importante, potenciales realistas, valores de difusión, solubilidad etc de especies ligeras, H (o sus isotopos) y He en metales líquidos podrá ser calculada complementando así la base de datos que presenta enormes incertidumbres.

Stopping power dependence of nitrogen sputtering yields in copper nitride films under swift-ion irradiation: Exciton model approach

Nitrogen sputtering yields as high as 104 atoms/ion, are obtained by irradiating N-rich-Cu3N films (N concentration: 33 ± 2 at.%) with Cu ions at energies in the range 10?42 MeV. The kinetics of N sputtering as a function of ion fluence is determined at several energies (stopping powers) for films deposited on both, glass and silicon substrates. The kinetic curves show that the amount of nitrogen release strongly increases with rising irradiation fluence up to reaching a saturation level at a low remaining nitrogen fraction (5?10%), in which no further nitrogen reduction is observed. The sputtering rate for nitrogen depletion is found to be independent of the substrate and to linearly increase with electronic stopping power (Se). A stopping power (Sth) threshold of ?3.5 keV/nm for nitrogen depletion has been estimated from extrapolation of the data. Experimental kinetic data have been analyzed within a bulk molecular recombination model. The microscopic mechanisms of the nitrogen depletion process are discussed in terms of a non-radiative exciton decay model. In particular, the estimated threshold is related to a minimum exciton density which is required to achieve efficient sputtering rates.